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Brunswick, Units 1 and 2, Submittal of Technical Specification Bases Revisions.

C4J Progress EnergyAPR 1 3 2006SERIAL: BSEP 06-0044U. S. Nuclear Regulatory CommissionAITN: Document Control DeskW'ashington, DC 20555-0001Subject: Brunswick Steam Electric Plant, Unit Nos. 1 and 2Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62Submittal of Technic...

Regulatory Guide 1.206, Section C.I.3, Design of Structures, Systems, Components, and Equipment, to Combined License Applications for Nuclear Power Plants (LWR Edition) (Preliminary Use).

Issued for Preliminary UseRev. 0 of RG 1.206, Page C.I.3-1C.I.3 Design of Structures, Systems, Components, and EquipmentChapter 3 of the final safety analysis report (FSAR) should identify, describe, and discuss theprincipal architectural and engineering design of those struc...

IR 05000483-06-011, on 04/11-06/16/2006 for Callaway Plant: Special Inspection to evaluate AmerenUE's discovery that component cooling water flow to the residual heat removal heat exchangers would not have been established until after the Postloss....

July 14, 2006Charles D. Naslund, Senior Vice President and Chief Nuclear OfficerUnion Electric CompanyP.O. Box 620Fulton, MO 65251 SUBJECT: CALLAWAY PLANT - NRC SPECIAL INSPECTION REPORT 05000483/2006011Dear Mr. Naslund:On April 11-14, 2006, the U.S. Nuclear Regulatory Com...

Limerick Generating Station, Units 1 and 2, License Amendment, Elimination of Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors (TAC MC2741 and MC2742).

April 13, 2005Mr. Christopher M. CranePresident and Chief Nuclear OfficerExelon Nuclear Exelon Generation Company, LLC200 Exelon Way, KSA 3-EKennett Square, PA 19348SUBJECT: LIMERICK GENERATING STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDME...

LER 05-004-00 for Brunswick, Units 1 & 2 re Loss of Electrical Power to Emergency Bus E1.

Progress EnergyJuly 11, 2005SERIAL: BSEP 05-0075 10 CFR 50.73U. S. Nuclear Regulatory CommissionATIN: Document Control DeskWashington, DC 20555-0001Subject: Brunswick Steam Electric Plant, Unit Nos. I and 2Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-72Licensee Ev...

McGuire February 2005-301 Exam 50-369 & 50-370/2005-301 FINAL Admin JPMS.

Final SubmittalMCGUIRE FEB 2005 EXAM50-369 & 370/2005-301FEBRUARY 7 - 15, 2005FEBRUARY 18, 2005 (written)1. Administrative Questions/JPMs2. In-plant JPMs3. Control Room JPMs (simulator JPMs)ES-301 Administrative Topics Outline Form ES-301-1Facility: _McGuire Date of Examinatio...

Enclosure for assessment ECCS pumps.

Enclosure Detailed Assessment of Generic Issue (GI)-193 The proposed issue was initially evaluated by a Generic Issue Review Panel (GIRP) (hereto referred to as the original GIRP) and determined the issue met the seven screening criteria. The original GIRP submitted an initi...

"Diablo Canyon Verification Program," Semimonthly Rept 24 for 821005-18.

Pacific Gas and Electric CompanySemimonthly Report No. 24Diablo Canyon Verification ProgramOctober 22, 1982SUMMARYThis is PGandE's twenty-fourth Semimonthly Status Report which summarizes theprogress of our design verification program from October 5, 1982, throughOctober 18, 1...

Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls.

WOLF CREEK TABLE OF CONTENTS CHAPTER 7.0 INSTRUMENTATION AND CONTROLS Section Page 7.1 INTRODUCTION 7.1-1 7.1.1 IDENTIFICATION OF SAFETY-RELATED...

Vogtle, Units 3 and 4 - Request for License Amendment and Exemption: Pipe Rupture Hazard and Flooding Analyses (LAR-17-010).

  Southern Nuclear               Operating Company, Inc.                     42 Inverness Center Parkway Birmingham, AL 35242 Tel 205.992.7006                                                                                                                                       ...

Forwards info NRC requested during 990610 telcon re questions resulting from Aug/Sept 1997 design insp at Diablo Canyon Power Plant.Proposed FSAR changes in response to Question 7 of Attachment A included in Attachment B.

CATZG'OarXREGULA1~ Y INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION PH3R:9910060146 DOC.DATE: 99/09/29 NOTARIZED: NOFACIL:50rp75 Di.ab3;o Canyon Nuclear Power Plant, Unit 1, Pacific Ga5Q;~2~~ Diablo Canyon Nuclear Power Plant, Unit 2, Pacific GaAiUTH. Nk"NAUTHOR AFFILIATION'O...

Waterford, Unit 3 - Application to Revise Technical Specifications to Adopt TSTF-545, Rev 3, "TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing," and to Request an Alternative to the ASME Code.

W3F1-2016-0036 10 CFR 50.9010 CFR 50.55aJuly 25, 2016U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555SUBJECT: Application to Revise Technical Sp...

Beaver Valley, Units 1 and 2 - Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan.

May 20, 2017FENOC™ FirstEnergy Nuclear Operating Company Marty L. Richey Site Vice President L-17-104 ATIN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, Licens...

Forwards response to Reactor Sys Branch request for addl info re open items,per 811007 telcon.Response will be incorporated into FSAR Amend 21.

REGULAR'OR'f iVFORMATION DlISTRIBUTION S TEM, (RIDS)ACCESSIOAi N>R 81'1 f 250484 DOC ~DA'TEI 81/10/27 NOTARIZED ~'ODOCKEil't 0FACILi:50:-397 WPPSS Nuc Ie'arPro Jecti, UnitI 2'i 'Hashing ton Publ ~i c'bwel 05090397AUTdl, NAMEl AU 1'HOR AF F ILI'ATiIONBOUCHElf1~~4/n o30 ~~~TABLE...

8/1/2011 - 8/5/2011 EPRI/NRC-RES Fire PRA Course: Principles of Human Reliability Analysis (HRA).

Principles of Human Reliability A l i (HRA) Analysis (HRA)Joint RES/EPRI Fire PRA Workshop 2011San Diego CA and Jacksonville FLA Collaboration of U.S. NRC Office of Nuclear Regulatory Research (RES) & Electric Power Research Institute (EPRI)Course Objectives• Introduce Human R...

Oyster Creek - Final Outlines (Folder 3).

ES-401 Written Examination Outline Form ES-401-1 Oyster Creek ILT 10-1 Facility: Date of Exam: 07/11/11NRC Exam Outline Tier Grou P K 1 K 2 RO KIA Category Points K K K K A A A 3 4 5 6 1 2 3 A 4 G * Tota I SRO-Only Points A2 G* Total 1. 1 3 4 3 3 4 3 20 4 3 7 Emergenc y 2 1 ...

FOIA/PA-2011-0118, FOIA/PA-2011-0119, FOIA/PA-2011-0120 - Resp 24 - Partial, Group Letter Y, Part 3 of 8.

Doerflein, LawrenceFrom:- Doerflein, LawrenceSent: Thursday, March 24, 2011 1:19 PMTo: Williams, ChristopherSubject: RE: Areva's Presentation on the Fukuchima EventthanksFrom: Williams, ChristopherSent: Thursday, March 24, 2011 12:37 PMTo: Doerflein, LawrenceSubject: FW: Areva...

Attachment 10 - EP-AA-1006, Revised Radiological Emergency Plan Annex Information for Quad Cities Nuclear Station.

ATTACHMENT 10REVISED RADIOLOGICAL EMERGENCY PLANANNEX INFORMATIONFORQUAD CITIES NUCLEAR POWER STATIONEP-AA-1 006Enclosures600Enclosure 10A - Revised EAL Comparison Matrix DocumentEnclosure 10B - Revised EAL Red-Line Basis DocumentsEnclosure 10C - Revised EAL Basis DocumentsI N...

Columbia, Final Safety Analysis Report, Amendment 63, Chapter 3, Figure 3.5-48 - Cantilever Barrier Structure to Page 3.6-101.

2'-0"4'-9"#6@10"#6 @ 10"#6 @ 12"Cantilever Barrier Structure910402.24 3.5-48FigureAmendment 53November 1998Form No. 960690Draw. No. Rev.Elevation Section A-APlanPlan1017L.9 H.3TurbineGen. BldgCorridorRadwasteandControlBldgCantileverBarrier WallsDoor Opn'gCantilever WallEL. 467...

IR 05000335/2014005, 05000389/2014005; on 10/01/2014 - 12/31/2014; on St. Lucie Nuclear Plant, Units 1 & 2; Problem Identification and Resolution.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 January 30, 2015 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420 ...

Diablo Canyon Power Plant, Units 1 and 2 - NRC Examination Report 05000275/2016301; 05000323/2016301

June 7, 2016 Mr. Edward D. Halpin, Senior Vice President, Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 SUBJECT: DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - NRC EXA...

Peach Bottom Atomic Power Station, Units 2 and 3 - Issuance of Amendments Re: Inservice Leak and Hydrostatic Testing Operation (CAC Nos. MF7208 and MF7209).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 9, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3 - ISSUANCE OF AMENDMENT...

University of Massachusetts, Lowell - Safety Analysis Report, (Chapters 1-7) - Redacted.

SAFETY ANALYSIS REPORT (CHAPTERS 1-7) University of Massachusetts Lowell Research Reactor (UMLRR) License R-125 Docket 50-223 (2015 REV. 0) REDACTED FOR PUBLIC RELEASEREDACTED FOR PUBLIC RELEASE TABLE OF CONTENTS CHAPTERS 1. THE FACILITY 2. SITE CHARACTERISTICS 3...

Waterford Steam Electric Station, Unit 3, Revision 309 to Final Safety Analysis Report, Chapter 9, Auxiliary Systems, Section 9.3.

WSES-FSAR-UNIT 3 9.3-1 Revision 307 (07/13) 9.3 PROCESS AUXILIARIES 9.3.1 COMPRESSED AIR SYSTEM 9.3.1.1 Design Bases (EC-41355, R307) The compressed air system, consisting of the Instrument and Service Air Systems, is designed to provide a reliable supply of dry, oil...

South Texas Project, Units 1 & 2 - Supplement 3 to Revised Pilot Submittal and Requests for Exemptions and License Amendment for a Risk-Informed Approach to Address Generic Safety Issue (GSl)-191 and Respond to Generic Letter (GL) 2004-02.

South Texas Pmiect Electric Ge11erati11g Station P.O. Box 28.9 Wadsworth, Texas 77481 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498 and STN 50-499 October 20, 2016 . NOC-A...